ML20209F832
| ML20209F832 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/30/1999 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-990630-01, PROC-990630-1, NUDOCS 9907160144 | |
| Download: ML20209F832 (63) | |
Text
o i X244 ALL I Document Control Desk Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission I Mail Station PI-137 Washington, DC 20555 ;
July 13,1999 Attached is a revision to the Offsite Dose Calculation Manual, Zion Annex, Chapter 12.
Please update your manual as follows:
Remove: I Zion, Chapter 12, Revision 3 Insert:
Zion, Chapter 12, Revision 4 Please sign below indicating your manual has been updated and that your controlled copy number is correct.
Name Date Return to:
Comed Procedures Clerk 1400 Opus Place,4th Floor Downers Grove, IL 00515
-or-Procedures Clerk 4th Floor ETW 111 0) u 9907igkhoM95 PDR PDR P
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ATTACIIMENT A
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Description of ODCM Changes for OSR/001/99
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P._agg Change Description /Brief Justification of Change l 12-l & 3 Remove defmition 12.1.1. " ACTION" and include in new definition 12.1.22.
" SURVEILLANCE" The definition for surveillance more accurately describes the three activities performed in section 12 with frequencies guided by Table 12.1-1. The three activities are; remedial measures for inoperable components, activities to verify component operability, and activities to ensure offsite dose limits verified. This definition more clearly establishes activities performed in this section.
12-1 A statement was added to the definition for " DOSE EQUIVALENT I-131" stating that the definition is not used in the defueled condition. Radioactive I iodine is no longer a concern due to decay since permanent cessation of operation.
12-2 A statement was added to the definition for " OPERATIONAL MODE" stating j n that the definition is not applicable in the defueled condition. The station is !
U defueled and will never enter an " operational mode" 12-3 The definition for " Ventilation Exhaust" was changed to " Gaseous EfIluent" and discussion of iodines was removed. Gaseous efiluent more accurately describes the whole system and iodine is no longer present due to decay and permanent cessation of operation. A statement was added to the definition for
" WASTE GAS HOLDUP SYSTEM" stating that the system is no longer used and useful in the defueled condition. This is consistent with the DSAR and the current plant configuration. Venting of plant systems and decay has eliminated all measurable noble gas from the waste gas system and its feeder systems. In the defueled configuration there is no means for future introduction into the waste gas system.
12-4 In Table 12.1-1 delineating frequency definitions removed (Refueling Cycle) from the frequency notation for "R" Maintaining the 18 month frequency but no longer tied to refueling as refueling is an obsolete activity.
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ZION Revision 4 June 1999 12.7.4 Maior Chanaes to Liauid and Gaseous Effluent Treatment Systems *" ]
Licensee-initiated major changes to the Effluent Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplementalinformation;
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
- 4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ frcm those previously estimated in the License application and amendments thereto;
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made:
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and Investigative Function.
- b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.
"* Licensees may choose to submit the information called for in this standard as part of the annual l FSAR update.
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, , ATTACIIMENT A Description of ODCM Changes for OSR/001/99 a
12-10 Eliminated the gas decay tank and its associated flow rate monitor. There is no activity present in the gas decay tanks or associated system requiring specific monitoring and automatic isolation. There is no functional need for a waste gas holdup system in the plant defueled condition. Eliminated the Air Ejector Off-gas Monitors. These monitors were only required in operational modes 1
& 2. The function of these monitors are not applicable in a permanently defaeled plant. The containment purge and vent section was clarified with the addition of Efiluent in the title. The paniculate containment purge monitors 1(2)RT-PR09C are eliminated. The current requirement is to have the containment SPING or the purge monitor available to purge. In the rare event that a purge is needed, the containment SPING is still required with its auto actuation function. Venting of containment should not be required in the defueled condition as integrity should never be set. However, in the event a vent is needed the monitoring provided by the containment SPING remains unchanged The applicable mode was changed to the condition " venting or purging" The title of section 2 was changed to "EfIluent Ventilation" to more {
accurately describe the monitors' function. The applicability was changed for j p)
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ORE 0014 to " supply or exhaust fans operating" to reflect the condition the monitor is designed to monitor. The applicability for 1(2)RIA-PR49 channels
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l & 5 was changed to "All Times" as this monitor should be available at all times to monitor any activity passing through the vent stack to the public. All iodine monitoring was eliminated as radioactive iodine is no longer a concern due to decay and permanent cessation of operation. The miscellaneous cubicle monitor ORT-PR12A was eliminated. This monitor as well as the iodine monitors were only required in operational modes 1,2,3,4 and as such have no applicability in the defueled condition. The applicability for the flow rate monitors for the vent stack was changed to " supply or exhaust fans operating" to reflect the condition the monitor is designed to monitor. The fuel building ,
area monitors were added to facilitate the ODCM as the guiding document as the monitors are removed from the Tech Specs. However, the changes do not i conflict / relax requirements in the current Tech Specs. This change adds an additional requirement above Tech Specs for ORE 0005 and ORT-AR03. The new requirement changes to whenever fuel is present to satisfy a new criticality monitoring requirernent as well as the Tech Spec fuel handling accident applicability.
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ATTACIIMENT A Description of ODCM Changes for OSR/001/99 O
12-5 Changed the general requirements to Plant monitoring instead of emuent monitoring and delineated the specific emuent requirements as for emuent monitors. This facilitated use of the ODCM as the guiding document for the component cooling monitors as they are ITDC but no longer applicable in current Tech Specs.
12-6 Added "Emuent" into the titles for the emuent monitors. Added a " plant System Monitors" for the component cooling monitors. Consistent with the definition " SURVEILLANCE" definition change changed Action to Surveillance. Changed Applicable Modes to Applicable Condition and changed applicability for the effluent monitors except the fire sump compositer to " liquid release through that pathway" The fire sump compositer was changed to "All Times" for clarification. The component cooling monitors were changed to " monitoring an active CC loop" More accurately describes the activity for which the monitor is required to perform its intended function.
12-7 Changed the word " ACTION" to " SURVEILLANCE" Added a statement to {
Surveillance 2 requiring development of a plan to return the monitor to service I ifit is inoperable for 30 days. Ensures the monitor does not remain inoperable indefinitely. Added Surveillance 4 for the component cooling monitors.
Maintains the current surveillance with the additional requirement to develop a plan to return the monitor to service ifit is inoperable for 30 days.
I 12-8 Changed the titles on sections 1-3 to more accurately describe the monitors as i emuent . monitors. Added a section for the component cooling monitors with the standard operability surveillances.
12-9 Changed the general monitoring requirements from " Gaseous Emuent" to
" Plant" and delineated the specific emuent requirements as for the emuent monitors only. This facilitates inclusion of Emergency and Fuel Building monitors into the ODCM as the guiding document instead of Tech Specs.
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, , ATTACIIMENT A m
Description of ODCM Changes for OSR/001/99 12-12 This is different than the current remedial surveillance. These monitors were moved to the ODCM from Tech Specs where they had an applicability of operational modes 1,2,3,4,7. Zion will never enter an operational mode again.
These monitors are not credited in the mitigation of any accident described in the DSAR. In the absence of radioactive iodine their charcoal beds no longer have a function. This surveillance is appropriate to ensure the monitors are available to perform monitoring functions described in the current GSEP.
Surveillance 15 was added for the new Control Room and TSC area monitors moved from Tech Specs to the ODCM. The surveillance was changed to include the ability to initiate an alternate means of monitoring with alarm capabilities. These monitors are for area habitability. Local alarming monitors would indicate the need to assess the area for habitability.
12-13 Operability surveillances were removed for those monitors deleted from the ODCM. Operability surveillances were included for the newly added fuel building area monitors. These new surveillances are consistent with those listed in current Tech Specs.
g 12-14 Arranged the emergency monitors into one group and delineated operability I 4 surveillances for the newly added Control Room and TSC monitors. The required surveillances did not change from current practice 12-15 Added a footnote for the fuel handling area monitors (consistent with current requirements) to source check daily during fuel handling activities.
12-16 In section 12.3.1.A.2. the requirement to have at least 200,000 gpm of dilution flow for release of radioactive liquid wastes was removed. This was too restrictive and conservative. The release requirements do not change. The station must meet release concentration limits. This change allows the freedom to adjust dilution and discharge rates to meet the limits. Again, section 12.3.1.B.3. was changed removing the requirement to have a circulation water pump operating on the discharge path during release. This was changed to require appropriate dilution and discharge flows are used to meet release concentration limits.
12-19 Requirements for analyzing for radioactive iodine were eliminated. Due to decay and permanent cessation of operation iodine is no longer present in the waste / effluent streams at Zion.
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4 ATTACIIMENT A . .
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Description of ODCM Changes for OSR/001/99 12-11 The steam line monitors and containment accident monitors were eliminated.
They were only applicable in operational modes. They are not required or applicable in the defueled condition. The vent stack accident monitors were '
relocated to the Emergency Monitoring section. An Emergency Monitoring section was created to facilitate the ODCM as the guidance document instead of Tech Specs. The monitors are no longer applicable in Tech Specs but must be controlled until the GSEP plan changes are approved by the NRC.
Monitoring for iodine has been eliminated as it is not a concern in the defueled condition. This section includes the Tech Support Center (TSC) SPING, the Control Room SPING and Area monitoring for these areas. This section also includes the high range vent stack noble gas channels.
12-12 This page lists the remedial activities required for each monitor if it is unavailable to perform its function when required by its associated applicable condition. The gas decay tank surveillance has been eliminated because the monitor has been eliminated. Current " action 8" was deleted as there was no associated monitor for this remedial activity. The surveillance for the vent stack flow panel was changed from a frequency of once per shift to once per day. This is consistent with the frequency for the vent stack monitor itself. i Also, the vent stack flow can be determined at any time from the number of exhaust fans operating per unit. The vent stack SPING mid and high range noble gas channel surveillance number changed from 10 to 9, but the actual remedial surveillance did not change. Current " Action 11" was deleted as the associated Fuel handling accident in containment monitors (AR04) were deleted. Current " Action 12" was deleted as there was no associated monitor for this remedial activity. The statement " collected with auxiliary sampling equipment" was deleted from the surveillance activity for the vent stack SPING particulate channel. The surveillance remains unchanged, this change allows freedom in determining how to meet the surveillance activity. A new Surveillance 12 was added for ORT-AR03. The surveillance is consistent with current practice with the additional requirement to perform daily area surveys.
The survey requirement was added to meet the added function of the monitor as a criticality monitor. Surveillance 13 and 14 were added for the other two fuel building area monitors. These remedial activities are consistent with current practice. For the Control Room and TSC SPING assigned Surveillance requirement 9.
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ZION Revision 4 June 1999 SPECIAL NOTE The requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur.
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ATTACIIMENT A - -
Description of ODCM Changes for OSR/001/99 12-21 Footnote (f) was changed to be consistent with the requireme:ds for the turbine building sump as delineated in Table 12.2-1. A sample will be collected once per day instead of once per shift. This is appropriate with no active secondary side available as a release path.
12-25 Thyroid dose was changed to organ dose to more accurately reflect the dose limit. Organ dose is the general dose requirement, the limitation on the thyroid would be included as an organ.
12-26 Eliminated gu decay tanks as a mode of release. This is consistent with the DSAR. The gas decay tanks have been vented and there is no process by which noble gas can be added to the waste gas system. Deleted footnote (a) from containment releases. The station can never " start-up, shutdown, or have power changes" For continuous vent stack release path, removed the requirement to collect and analyze for radioactive iodine. Due to decay and permanent cessation of operation iodine is no longer present in the waste /emuent streams at Zion.
12-27 Deleted footnote (a). The station can never " start-up, shutdown, or have power changes" 12-32 To clarify and make consistent throughout this section, changed " Ventilation Exhaust" and "Gaseus Radwaste" to " Gaseous Emuent" Remove mention of the Waste Gas Hold-Up system. It is no longer used and useful in the defueled ,
condition. j 12-36 Removed requirements for collection and analysis of radioactive iodine. Due to decay and permanent cessation of operation iodine is no longer present in the waste /emuent streams at Zion.
12-40 Deleted footnote regarding iodine analysis. Due to decay and permanent cessation of operation iodine is no longer present in the waste /emuent streams at Zion.
12-52 Changed " Gaseous Radwaste" to " Gaseous Emuent" to more accurately describe the system function.
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ZION Revision 4 June 1999
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1 CHAPTER 12 I i
k RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (RETS)
TABLE OF CONTENTS I
PAGE 12.1 DEFINITIONS 12-1 !
12.2 INSTRUMENTATION
- 1. Radioactive Liquid Plant Monitoring Instrumentation 12-5
- 2. Radioactive Plant Monitoring Instrumentation 12-9 12.3 LIQUID EFFLUENTS
- 1. Concentration 12-16
- 2. Dose 12-22
- 3. Liquid Radwaste Treatment System 12-24 12.4 GASEOUS EFFLUENTS
- 1. Dose Rate 12-25
- 2. Dose - Noble Gases 12-28
- 4. Gaseous Effluent Treatment System 12-32 l U 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- 1. Monitoring Program 12-33
- 2. Land Use Census 12-45
- 3. Interlaboratory Comparison Program 12-46 12.6 PROCESS CONTROL PROGRAM (PCP)
- 1. PCP Program Requirement 12-47
- 2. Changes to the PCP 12-47 12.7 REPORTING REQUIREMENTS
- 3. Offsite Dose Calculation Manual (ODCM) 12-51
- 4. Major Changes to Liquid and Gaseous Effluent Treatment Systems 12-52 l l
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ZION Revision 4 June 1999 REVISION 4 O
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ZION Revision 4 June 1999 12.1 DEFINITIONS
' 12.1.1 A BATCH RELEASE is the discharge of liquid wastes of a discrete vo!ume. Prior to sampling l for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.
12.1.2 A CHANNEL cal.dBRATION, shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CAllBRATION shall encompass the entire channelincluding the sensors (where possible),
alarm interlock and/or trip functions and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measunr.g the same parameter.
12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:
- a. Instruments-The injection of a simulated signal (s) into the channel as close to the primary sensor (s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.
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- b. Logics-The application of input signa ls, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where
[ practicable, the test shallinclude the operation of the ACTUATED EQUIPMENT V] as well (i.e. pumps will be started, valves operated, etc.).
12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the quantity of hquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
12.1.6 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release).
12.1.7 A CONTINUOUS SAMPLING FREQUENCY is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements).
12.1 e DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, 1-133,1-134, and 1-135 actually present. The Thyroid Dose Conversion f actors used for this calculation shall be those listed in Table 111 of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109 Rev.1, dated October,1977. This definition is not used in the defueled condition. Decay has eliminated all concerns related to radioactive iodine.
12.1.9 MEMBER OF THE PUBLIC means any individual except when that individualis receiving an occupational dose.
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ZION Revision 4 June 1999 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
UST OF TABLES l PAGE
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i 12.1 1 Surveillance Frequency Notations 12-4 ,
l 12.2 1 Radioactive Liquid Plant Monitoring Instrumentation 12-6 12.2-2 Radioactive Liquid Plant Monitoring Instrumentation Surveillance 12-8 12.2-3 Radioactive Plant Monitoring Instrumentation 12-10 12.2-4 Radioactive Plant Monitoring Instrumentation Surveillance 12-13 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Effluents 12-18 12.3-2 Radioactive Liquid Effluent Sampling and Analysis Surveillance 12-19
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12.4 1 Radioactive Gaseous Effluent Sampling and Analysis Program 12-26 12.5-1 Radiological Environmental Monitoring Program 12-36 1
12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-41 1 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-42 0
212r4 doc 12-iv
ZION Revision 4 June 1999 12.1.22 SU. rye.R.J.A.NCE shall be those parts of the sections which prescribe remedial measures Q required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded.
12.1.23 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1 1, 12.1.24 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
12.1.25 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee.
12.1.26 QMEQ.QS..EEEWENT TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing l ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the l purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect on noble gas effluents. The iodine removal function is no longer used in the defueled condition. l 12.1.27 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a venting process.
12.1.28 WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total O radioactivity prior to release to the environment. This system is no longer used and useful in the defueled condition.
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ZION Revision 4 June 1999 12.1.10 OCCUPATIONAL DOSE means the dose received by an individualin the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupat;onal dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.
12.1.11 OPERABLE. - A system, subsystem, train, component or device shall be OPERABLE or have l OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
12.1.12 OPERATING is defined as performing the intended function in the intended manner.
12.1.13 The OPERATING CYCLE shall be the interval between the end of one major refueling outage and the end of the next subsequent major refueling outage per unit.
12.1.14 An OPERATIONAL MODE (i.e., Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the Technical Specifications, when fuel assemblies are present in the reactor vessel. This definition as not applicable in a permanently defueled condition. l 12.1.15 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the &
disposal of solid radioactive waste.
12.1.16 PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement.
12.1.17 RATED THERMAL POWER shall be a total steady state reactor core heat transfer rate to the reactor coolant of 3250 MWt.
12.1.18 The REACTOR PRESSI1RE shall be in the pressure in the steam space of the pressurizer.
i 12.1.19 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.
12.1.20 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements.
12.1.21 A COURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
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ZION Revis!on 4 June 1999 A- 12.2 INSTRUMENTATION U 12.2.1 Radioactive Liquid Plant Monitoring instrumentation l Operability Reauirements 12.2.1. A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND. the radioactive liquid effluent monitoring instrumentation channels shall have their alarm / trip setpoints set to ensure that the limits of Section 12.3.1.A are met.
Acolicability: As indicated in Table 12.2-3.
l Action 1, With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1.A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
- 2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.
Surveillance Reauirements 12.2.1.B.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures l as described in the ODCM.
12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated l OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2.
Bases 12.2.1.C The radioactive liquid plant monitoring inst.umentation is provided to indicate abnormal radiological conditions within the plant, ANQ, The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10CFR Part 50. l l
zi2r4 doc 12-5
ZION Revision 4 June 1999 TABLE 12.1 1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY
- S (Shiftly) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D (Daily) At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days R At least once per 18 months l S/U (Startup) Prior to reactor startup P (Prior) Complete prior to start of release EFPM At least once per effective full power month N/A Not Applicable Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. These frequency notations do not apply to the Radiological Environmental Monitoring Program as described in Section 12.5.
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ZION Revision 4 June 1999
!f~) TABLE 12 2-1 v
RADIOACTIVE LIQUID PLAN.T MONITORING INSTRUMENTATION l (Cont'd)
SURVEILLANCE 1 With one of the LDT monitors inoperable, all LDT releases shall be made l through the OPERABLE monitored pathway. If both monitors are inoperable, effluent releases from the tank may continue for up to 14 days, provided that prior to initiating the release:
- 1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and
- 2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; Otherwi.4e, suspend release of radioactive effluents via this pathway.
SURVEILLANCE 2 With the number of channels OPERABLE less the minimum number required, l effluent releases via this pathway may continue, provided that at least once per day grab samples are analyzed for gross radioactivity (beta / gamma or isotopic) at a lower limit of detection (LLD) as specified in Table 12.3-2. Restore the i channel to operable status within 30 days or conduct a station review to O determine a plan of action to restore the channel to operable status. l SURVEILLANCE 3 With the number of channels OPERABLE less than the minimum number l required, effluent releases via this pathway may continue, for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
SURVEILLANCE 4 With the number of channels OPERABLE less than the minimum required, obtain and analyze a component cooling sample once per day. If the monitor is not returned to service within 30 days, conduct a station review to determine a plan of action to return the channel to operable status.
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ZION Revision 4 June 1999 12.2.2 Radioactive Plant Monitoring Instrumentation j Operability Rgquirements 12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, b.N.Q, the radioactive gaseous effluent monitoring instrumentation shall have their alarm / trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 1?.4.1.A are met.
boolicability: As indicated in Table 12.2-3.
l Action
- 1. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effiuents monitored by the affected channel or declare the channel inoperable.
- 2. With one or more radioactive plant monitoring instrumentation channels inoperable, initiate the SURVElLLANCE requirement as delineated in Table 12.2-3.
Surveillance Reauirements 12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as described l In the ODCM.
12.2.2.B.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE l by performance of a CHANNEL CHECK SOURCE CHECK, CHANNEL CALIBRATION and
- O CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4.
Bases 12.2.2.C The radioactive plant monitoring instrumentation is provided to indicate abnormal radiological conditions within the plant,6NQ, The radioactive gaseous effluent instrumentation is provided to monitor, record and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20.
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ZION Revision 4 June 1999 MINIMUM
- p. CHANNELS APPLICABLE g INSTRUMENT - OPERABLE .EURVE.lLIANQE CQNDOQN l
- 4. Empfgg.ngy.,Monit.oritig l
A. Control Room Process
-1, ORIA-PR29A (Channel 1) 1 9 All Times
- 2. . ORIA-PR29E (Channel 5) 1 9 All Times
- 3. ORIA-PR29G (Channel 7) 1 9 All Times B. Technical Support Center Process
- 1. ORIA-PR32A (Channel 1) 1 9 All Times
- 2. ORIA-PR32E (Channel 5) 1 9 All Times
- 3. . ORIA-PR32G (Channel 7) 1 9 All Times C. Control Room Area -
- 1. ORE 0001 1 15 All Times D. Technical Support Center Area
- 1. ORE-AR31 1 15 All Times
- 2. ORE-AR32 1 15 All Times
- 3. ORE-AR33 1 15 All Times E. Ventilation 1, 1RIA-PR49 (Channel 7) 1 9 All Times
- 2. 2RIA-PR49 (Channel 7) 1 9 All Times O 3.
4.
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ZION Revision 4 June 1999 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION l MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE _C.ONDlI).ON_. l
- 1. Ef.f).uent Containment Purae or Vent l A. Particulate Monitor
- 1. 1R-PR40A (Channel 1) 1 6', 7 2 Venting or Purging
- 2. 2R-PR40A (Channel 1) 1 6', 7 2 Venting or Purging
- 2. Eff!uent Ventilation A. Gas Activity Monitor
- 1. OR-0014 1 10 Supply or Exhaust Fans Operating
- 2. 1R-PR49E (Channel 5) 1 10 All times
- 3. 2R-PR49E (Channel 5) 1 10 All times B. Particulate Monitor
- 1. 1LP-084 1 8 Supply or Exhaust Fans Operating
- 2. 2LP-084 1 8 Supply or Exhaust Fans Operating
- 3. Eupl.B.uild.ing.Mqnit.o. ring A. Area Monitoring
- 1. ORT-AR03 1 12 When fuelis present
- 2. ORE 0005 1 14 When fuel is present
- 3. ORT-AR13 1 13 When fuel building crane is operated in bypass mode l During VENTING
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ZION Revision 4 June 1999 TABLE 12 2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION l (Cont'd)
TABLE NOTATIONS SURVEILLANCE 6 - With the number of channels OPERABLE less than the minimum number required. l effluent releases via this pathway may continue for up to 30 days provided grab samples are obtained and analyzed for gross activity at least once per day.
SURVElLLANCE 7 - With the number of channels OPERABLE less than the minimum number required, l and no redundant monitor OPERABLE in this flow path, immediately suspend PURGING of radioactive effluents via this pathway.
SURVEILLANCE 8 - With the number of OPERABLE channels less than the minimum number required, l effluent releases via this pathway may continue provided the effluent flow rate is estimated at least once per day while release is in progress. l SURVEILLANCE 9 - With the number of channels OPERABLE less than the minimum number required, l restore the inoperable monitor to OPERABLE status within 30 days or establish an alternato means of monitoring the parameter. i SURVEILLANCE 10 - With the number of OPERABLE channels less than the minimum number required. l restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent releases via this pathway may continue provided grab samples are obtained and analyzed for gross activity at least once per day.
SURVEILLANCE 11 - With the number of OPERABLE channels less than the minimum number required, l restore the channel to OPERABLE status within 30 days or conduct a station review to determine a plan of action to restore the channel to OPERABLE status. Effluent release via this pathway may continue provided grab samples are continuously collected as required in Table 12.4-1. l SURVEILLANCE 12 With the number of channels OPERABLE less than the minimum required, stop all movement of fuel within the spent fuel pool and crane operation with loads over the spent fuel pool AND perform area surveys of the monitored area at least once per day.-
SURVEILLANCE 13 With the number of channels OPERABLE less than the minimum required, stop operation of overhead crane in bypass after placing loads in safe condition.
SURVEILLANCE 14 Perform area surveys of the monitored area at least once per day. l
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SURVEILLANCE 15 Establish an alternate means of monitoring with alarm capabilities OR perform area I survey of the monitored area at least once per day.
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ZION Revision 4 June 1999 r^s Table 12.2-4
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RADIOACTIVE ELANT MONITORING INSTRUMENTATION SURVEILLANCE l (Cont'd)
TABLE NOTATIONS (1) CHANNEL CALIBRATION shallinclude performance of a CHANNEL FUNCTIONAL TEST. l (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that Control Room alarm annunciation occurs if any of the following conditions exist (if the l capability is installed):
{
a) Instrument indicates measured levels above the alarm setpoint.
b) Circuit failure. }
c) Instrument indicates a downscale failure.
Instrument controls not set in " operate" mode. ]
d) ;
i (3) Daily during operations of overhead crane in bypass mode.
(4) Daily during fuel handling operations or load handling operations in or above the spent fuel pool. j
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ZION Revision 4 June 1999 Bases 12.3.1.C This Section is provided to ensure that the concentration of radioactive inaterials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001 20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section ll.A design objectives of Appendix 1,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301.
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l ZION Revision 4 June 1999 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Recuirements 12.3.1.A.1 The concentration of radioactive material rel eased from the site to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrations shall be limited to the values listed in Table 12.3-1.
12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1. are not exceeded.
Apolicability: At all times.
Action
- 1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1. {
immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.
Surveillance Reauirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1. l 12.3.1.B.2 Post-release analysos of samples compos;ted from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall bc used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. j 12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points sha!!
be determined by collection and analysis of samples in accordance with Table 12.3-2.
The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1.
12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1.
zt2r4 coe O
12-16
ZION Revision 4 June 1999 TABLE 12.3-2 O
i RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE l MINIMUM LOWER LIMIT OF LIQUID RELEASE SAMPLING ANALYSIS TYPE OF DETECTION (LLD)
TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi/ml)(a,e) l A. Lake Discharge Prior to Each Release Prior to Each Principal Gamma SE-7 Tank (c) Release Emitters (e)
P M Dissolved and 1E-5 One Batch /M(c) Entrained Gases (Gamma Emitters)
P M Tritium 1 E-5 Each Batch (c) Composite (b)
Gross Alpha 1 E-7 P Q Sr-89, Sr 90 SE-8 Each Batch (c) Composite (b)
Fe-55 1 E-6 B. Turbine Building. Continuous During W Principal Gamma SE 7 Fire Sump (f) Release (d) Emitters (e)
Dissolved and 1 E-5 Entrained Gases
- b. (Gamma Emitters)
Continuous (d) M Tritium 1 E-5 Composite (b)
Gross Alpha 1 E-7 Continuous (d) Q Sr-89, Sr-90 SE-8 i Composite (b) I Fe-55 1 E-6 .
l C. Waste Prior to each Release Prior to each Principal Gamma SE-7 Neutralizing Tank Release Emitters (e)
P M Tritium 1 E-5 Each Batch (c) Composite (b)
Gross Alpha 1 E-7 1
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l zt2r4 doc j2 3g
ZION Revision 4 June 1999 TABLE 12.3-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID EFFLUENTS NUCLIDE A(nCi/m0*
Kr-85m 2 X 10" Kr-85 5 X 10" Kr-87 4 X 10~5 Kr-88 9 X 10-5 Ar-41 7 X 10*
Xe-131m 7 X 10" Xe-133m 5 X 10" Xe-133 6 X 10" Xe-135m 2 X 10" Xe-135 2 X 10"
- Computed from Equation 20 of ICRP Publication 2(1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0.
O 212r4 doc j 7,3 g a
ZION Revision 4 June 1999 TABLE 121-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)
TABLE NOTATIONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much grcater concentrations. Under these circumstances, it wik be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.
- b. A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the m1thod of sampling employed results in a specimen which is representative of the liquids releas ad.
- 1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the ctmposite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- 2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity) is maintained.
- c. A BATCH RELEASE is the discharge of Iquid wastes of a discrete volume. Prior to sampling for O analyses, each batch shall be isolated, and then thoroughly mixed to assure representative V sampling.
- d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the l following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cv 137. Ce-141, !
and Ce-144. This list does not mean that only these nuclides are to be detected ard reported.
Other peaks which are measurable and identifiable, together with the above nuchce shall also !
be identified and reported. Nuclides which are below the LLD for the analyses shall be reported j as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for ~
that nuclide. The "less than" values shall not be used in the required dose calculations.
- f. If the fire sump composite sampler is inoperable, grab samples shall be taken from the turbine building fire sump once per day.
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. .l ZION Revision 4 June 1999 l l
. l TABLE 12.3-2
)
RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd)
TABLE NOTATIONS
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.66 s p A E
- V 2.22 Y
- exp (-AAt)
Where:
LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sois the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A = 1.0) for gross alpha, strontium, and tritium measurement.
E is the counting efficiency (as counts per gamma),
V is the sample size (in units of mass or volume),
2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)
A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).
The value of soused in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples l Typical values of E, V, Y, and at shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within i one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for tne !
quantitative analysis for that radionuclide.
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ZION Revision 4 June 1999 S_ases 12.3.2.C This Section is provided to implement the requirements of Sections ll.A Ill.A and IV.A of Appendix 1,10CFR Part 50. The limiting Condition of Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix ! that confomlance with the guides of Appendix l be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1. Revision 1 October 1977 and Regulatory Guides 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.
This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system.
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O 212r4 doc 12-23
i ZION Rsvision 4 June 1999 l 12.3.2 Dose Onerability Reauirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED l AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited: l
- 1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- 2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Applicability; At all times.
Action
- 1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. Demonstrate that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard. The radiation exposure analysis shall use methods prescribed in the ODCM.
Surveillance Reauirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days.
O 212r4 doc j 7,pp
ZION Revision 4 June 1999 12.4 GASEOUS EFFLUENTS
-Q 12.4.1 Dose Rate Operatino Reauirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Zion Staticn ODCM Annex, Appendix F.
Figure F 1), shall be limited to the following:
- 1. For noble gases: Less than or equal to 500 mrem /yr to the whole body and less than or equal to 3000 mrem /yr to the skin, and
- 2. For lodine-131, lodine-133, tritium and all radionuclides in particulate form with j half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
J J
A olicabilitv: At all times.
J Action With a release exceeding the above limits, immediately reduce the release rate to within the above limits.
. Surveillance Reauiremente 12.4.1.B.1 The dose rate due to radioactive materials in gaseous effluents shall be determined to l
be within the prescribed limits in accordance with the methods and procedures of the '
ODCM.
O 12.4.1.B.2 The dose rate due to radioactive materials, other than noble gases in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table ,
12.4-1. '
I Bases 12.4.1.C This Section is provided to ensure that the dose at or beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR Part 20.1301. The specified release-rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation l pathway to less than or equal to 1500 mrem / year. For purposes of calculating dose resulting from airbome releases, the stack is considered a ground-level release.
O V
212r4 doc 12-25
ZION Rsvision 4 June 1999 12.3.3 Liquid Radwaste Treatment System Operability Reauirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE
- and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Zion Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.
- The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.
6policability: At all times.
Action With the Liquid Radwaste Treatment System inoperable for more than 19 days or with radioactive liquid waste bein0 discharged without treatment and is excess of the above limits, retum the system to OPERABLE status and place the appropriate portions of the system in use.
Surveillance Reauirements 12.3.3.B Doses due to liquid releases from the site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully utilized.
Bases 12.3.'3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Section implements the requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section ll.D of Appendix ! to 10CFR Part 50.
The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10CFR Part 50, for liquid effluents.
O 212r4 doc 12 24
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ZION Revision 4 June 1999 1
TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd)
IABLE NOTATIONS
- a. Deleted
{
- b. The ratio of the sample flow rate to the sampled stream flow rate shall Le known for the time period in Section 12.4.1.
- c. The particulate filter (s) shall be saved for a quarterly composite analysis for Sr-89 and Sr-90.
- d. For gaseous emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide,
- e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radioauclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample Nuclides which are below the LLD for the analyses A shall not be reported as being at the LLD level for that nuclide. i
- f. The LLD is defined in Notation a of Table 12.3-2.
- g. Refer to Table 12.2-3 for required actions when the noble gas monitor is not in service. i
- h. Sampling interruptions of short duration for routine activities, e.g. filter replacement, do not constitute a deviation from the requirements for continuous sampling.
L l
212r4 doc j2 27 l
ZION Revision 4 June 1999
~
TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF GASEOUS RELEASE SAMPLING LOWER LIMIT OF ANALYSIS ACTIVITY TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)
(pCi/cc)(f)
A. Deleted l B. Containment Vent Prior to Each Prior to Each Noble Gases 1 E-4 and Purge Release Release Principal Garama Emitters (d)
Tritium 1 E-6 C. Continuous Grab (b) Monthly Noble Gases 1 E-4 Principal Gamma Ventiletion Stack Emitters (d) for both (2) units Tritium 1 E-6 Continuous (b)(h) Weekly (c) Particulate 1 E-11 Principal Gamma Emitters (e)
Composite Quarterly Sr-89 Particulate 1 E-11 Sr-90 Particulate 1 E-11 Gross Alpha 1 E-11 Continuous (g)(h) N.A. Noble Gases, 1 E-6 Noble Gas Monitor ma I
l l
212r4 doc jp,pg i
. s .
ZION Revision 4 June 1999 7,3 Bases 12.4.2.C This Sedion implements the requirements of Sections ll.B. Ill.A and IV.A of Appendix 1, 10CFR Part 50. The Operability Requirements implement the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix ! is to be shown by calculation procedures based on models and data such that the actual exposure of an indMda' through the appropriate pathways is unlikely to be substantially underestimated.
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U'N zi2r4 doc 12-29
ZION Revision 4 June 1999 12.4.2 Dose - Noble Gases Operability Reauirements 12.4.2.A The air dose due to noble gases released in gaseous effluents from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
- 2. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
Acolicability: At all times Action
- 1. With the calculated air dose from gaseous effluents exceeding the above limits, define the corrective action (s) to be taken to ensure that future releases are in compliance with Section 12.4.2.A.
- 2. With the calculated air dose from radioactive noble gases in gaseous efflucats exceeding twice the limits of Section 12.4.2.A:
- a. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited g'p to less than or equal to 75 mrem) over 12 consecutive months.
- b. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluents pathways and direct radiation) are less than the 40 CFR Part 190 Standard.
Surveillance Reauirements 12.4.2.B Cumulative dose contributions for the current calendar quarter and current caleadar year for noble gases shall be determined in accordance with the methodologies and parameters of the ODCM at least once every 31 days.
O 212r4 doc 12-28
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ZION Revision 4 June 1999 O.. Bases 12.4.3.C This Section implements the requirements of Sections ll.C, Ill.A and IV.A ef Appendix 1, 10CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specJied in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rete specifications far radioiodines, radioactive material in particulate form and radiciodines other than noble gases are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1)individualinhalation of airborne radionuclides,
- 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man.
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zi2r4 doc 12-31
ZION Revision 4 June 1999 12.4.3 Dose - I-131,1-133, Tritium, and Radioactive Material in Particulate Form Operability Recuirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from 1-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and
- 2. During any calendar year: Less than or equal to 15 mrem to any organ.
Apolicabilitv: At all times.
Action With the calculated dose from the release of lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:
- 1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.
- 2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods ,
prescribed in the ODCM. '
Surveillance Recuirements 12.4.3.B Cumulative dose contribution for the current calendar quarter and current calendar year l for 1-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters {
in the ODCM at least once per 31 days.
l Ol l z12r4 doc 12-30 l
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ZION Revision 4 June 1999 ry 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
( )
12.5.1 61onitoring Program Qperability Reouirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.
Applicabilitv: At all times.
Action
- 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1 prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person / business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule shall be described in the
[N Annual Radiological Environmental Operating Report.
t V) 2. With the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3.
When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + . > 1.0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not raquired if the measured level of radioactivity was not the result of plant effluents; however, in such a event, the condition shall be reported and desenbed in the Annual Radiological Environmental Operating Report.
- The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC shall be indicated in the report.
V 212r4 doc 12-33
. / .
ZION Revision 4 June 1999 12.4.4 Gaseous Effluent Treatment System l Operability Reauirements 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE
- and l appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, fram each unit, to areas at or beyond the SITE BOUNDARY (see Zion Station ODCM Annex, Appendix F, FigLre F-1) would exceed:
- 1. 0.2 mrad to air from gamma radiation, or
- 2. 0.4 mrad to air from beta radiation, or
- 3. 0.3 mrem to any organ.
- The installed GASEOUS EFFLUENT TREATMENT SYSTEM shall be considered l OPERABLE by meetings Section 12.4.1,12.4.2 and/or 12.4.3, as applicable.
Aoolicability: At all times.
Action: With the Gaseous Effluent Treatment System inoperable for more than 30 days l
[
or with radioactive gaseous waste being discharged without treatment and in !
excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use.
Surveillance Reauirements 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologies and parameters in the ODCM when the Gaseous Effluent l Treatment Systems are not being fully utilized. !
I Bases l l
12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM ensures that l the system will be available for use whenever gaseous effluents require treatment prior l
to release to the environment. l The requirement that the appropriate portions of this system be used when specified !
provides reasonable assurance that the releases of radioactive materials in gaseous l effluents will be kept "as low as is reasonably achievable." This section implements the requirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50 and the design objective given in Section ll.D of Appendix l to 10CFR50. The specified limits governing the use of appropriate portions of the Gaseous Effluent Treatment l System were specified as a 2% fraction of the dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10CFR50, for gaseous effluents.
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212r4 doc 12-32
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ZION Revision 4 June 1999 (O Interpretations 12.5.1.0 Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers (6.2 miles)." Drinking water supply is defined as water l )
taken from river, lakes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one north /one south) within 10 kilometers shall be sampled as drinking water indicator locations, and two other locations (one north /one south) beyond 10 kilometers shall be sampled as controllocations.
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212r4 doc 12-35
a > .
ZION Revision 4 June 1999
- 3. If the sample type or sampling location (s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable altemative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.
Prepare and submit a controlled version of the ODCM within 180 days including l a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples.
Surveillance Reauirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3.
Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implement: Section IV.B.2 of Appendix l to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
The initially specified monitoring program will be effective for at least 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories.
It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal Chem.
40, 586-93 (1968), and Gartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
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e ~ .e ZION Revision 4 June 1999
, , TABLE 12.5-3 (Continued)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS
^
TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report, (2) Required 'Jetection capabilities for thermoluminescent dosimeters used for environntental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive materialin a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:
4.66 So + 3/to LLD = ----------------------
(E) (V) (2.22) (Y) (exp (-).at))
4.66 So LLD ~ ----------------------
q (E) (V) (2.22) (Y) (exp (-).At))
]
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so = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),
41'otal Counts Ib E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable,
). = the radioactive decay constant for the particular radionuclide (sec"),
to = counting time of the background or blank (minutes), and O
212r4 doc 12-43
49 n 9 o 9 i1 is e .
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,e ZION Revision 4 June 1999 1'2.5.2 l'AND USE CENSUS O Operability Reauirements 12.5.2.A A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 mi) the location, in each of the following meteorological sectors, A, J, K, L, M, N, P, Q, and R, of the nearest milk animal, the nearest residence", and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.
Acolicability: At all times.
' Action:
With a Land Use Census identifying location (s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.
The nearest industrial facility shall also be documented if closer than the nearest residence.
O h Surveillance Reauirements 12.5.2.B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per calendar year using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.
Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological l Environmental Monitoring Program given in the ODCM are made if required by the results of this census.
This census satisfies the requirements of Section IV.B.3 of Appendix i to 10 CFR Part
- 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.
D (V
zi2r4 doc 12-45
e .
ZION Revision 4 June 1999 TABLE 12.5-3 (Continued)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATi'ONS At = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).
Typical values of E, V, Y, and 41 should be used in the calculation.
It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
(4) If no drinking water pathway exists, the value of 15 pCill may be used.
(5) A value of 0.5 pCill shall be used when the animals are on pasture (May through October) and a value of 5 pCi/l shall be used at all other times (November through Aprit).
(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide.
(7) This is the minimum required LLD, however, environmental samples analyzed off-site will be required to use 200 pCi/l.
O zi2r4 dx 12-44
.o s ZION Revision 4 June 1999 l
12.6 p.B.QCESS CONTROL _ PROGRAM @.CP) P 12.6.1 PCP Program Req.uirements Contains the requirements and methodology for the current formulas, sampling, analyses, tests, and determinations performed to ensure the processing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:
e 10CFR Parts 20,61, and 71
. State Regulations o' Burial Site Requirements
- Other Requirements Goveming the Shipping and Burial of Radioactive Waste 12.6.2 Changes to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.
12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and Shall contain a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and acceptance by the Onsite Review and investigative Function and the approval of the Decommissioning Plant Manager.
I O
zi2r4 m 12-47
e ZION Revision 4 June 1999 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Reouirements 1
12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1.
Apolicability: At all times.
Action:
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commiss;on in the Annual Radiological Environmental Operating Report.
Surveillance Reouirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report.
Bases 12.5.3.C The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental samples matrices are performed as part of the quality assurance program for environmental monitoriiS in order to temonstrate that the results are valid for the purposes of Section IV.B.2 of Apoendix I to 10 CFR Part 50.
i Ol zi2r4 doc j 7,4g l
l
e o
- ZION Revision 4 June 1999 f~
(w The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."
12.7.2 Annual Radioactive Effluent Release Report" The Annual Radioactive Effluent Release Reports shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,
- Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materialin Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1. June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive material in liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive materialin gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period.
The Annual Radioactive Effluent Release Report shallincluoe any changes made during the
/ reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.7.4.
The Annual Radioactive Effluent Release Report shall also include the following: an explanation l as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not I corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limit; of Technical Specification 3.11 or 3.12, respectively. l 12.7.2.1 Exceptions to Regulatory Guide 1.21 Repolting Requirements:
- a. All references to " semiannual" are not applicable. The report will be submitted according to Technical Specifications.
- b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included,
- c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.
O z12r4 doc 12-49 i
> -. 1 l
ZION Revision 4 June 1999 i I
12.7 REPORTING REQUIREMENTS 12.7.1 Annual Radioloaical Environmental Operatina Report
- Routine Annual Radiological Environmental Operating Report covering the operation of the Unit (s) during the previous calendar year shall be submitted according to Technical Specification 6.6.1.C. The Annual Radiological Environmental Operating Report shall l include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The Annual Radiological Environmental Operating Report shallinclude the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.
The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form o, an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
A single submittal may be made for a multiple unit station.
O 212r4 dx j 7,4g I
qo w ZION Revision 4 Juns1999
] ';A
- 12.7.3 Offsite Dose Calculation Manual (ODCM) 12.7.3.1 Changes to the ODCM
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.2. This documentation shall contain: l
- 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s); and
- 2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- 3. Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review Function.
- b. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the
/"N date (e.g., month / year) the change was implemented, i
i l
l D l 212r4 doc '
12-51
~ ~o ZION Revision 4 June 1999
- d. Organ doses to the maximally exposed individual in unrestricted areas frDm ,'
radioactive iodine and radioactive material in particulate form from all exposure pathways will be provided. Associated population dose is not required to be included.
- e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated population dose is not required to be included.
- f. Total body doses to the population and average doses to individuals in the population from all receiving-water-related pathways are not required to be included.
- g. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site and beyond will not be included.
" A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
l O
O 212r4 d*
12-50
. . . ~ _